Refined Analytical Method for 129I in Cement-Solidified Spent Ion Exchange Resins

• 발행기관: 한국방사성폐기물학회
• 저자명: Gi Yong Kim Kyunghun Jung Jai Il Park Tae-Hong Park
• 간행물 정보: 『Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT)』Vol.23 No.2, 225~237쪽, 전체 13쪽
• 주제분류: 공학 > 공학일반
• 파일형태: PDF
• 발행일자: 2025.06.30

국문 초록

Spent ion exchange resins (SIERs) are commonly immobilized in cement, necessitating the reliable determination of radionuclides in cement-based waste forms. This study developed a simple and practical method for quantifying 129I, a key radionuclide in low- and intermediate-level radioactive waste (LILW) disposal. Investigation into iodine behavior during leaching, extraction, and precipitation revealed that iodate (IO3⁻) readily adsorbs onto cement minerals, reducing chemical recovery in extraction-based methods. To mitigate this, we implemented an in-situ conversion of IO3⁻ to I2, improving chemical yields from 58% to 93% in fine cement samples (φ < 0.5 mm). The optimized method was further applied to cement containing anion exchange resins, where increasing resin content led to a decrease in chemical yield, reaching 51% at 10wt% resin loading, close to the practical limit in ordinary Portland cement (OPC) waste forms. This decline was likely attributed to the re-adsorption of iodide (I⁻) onto the resins during the conversion of IO3⁻ to I2. Despite this, measured 129I activities closely matched expected values, demonstrating its reliability for routine analysis of cement-based radioactive waste.

목차

1. Introduction

2. Materials and Methods

3. Results and Discussion

4. Conclusions

Conflict of Interest

Acknowledgements

REFERENCES

키워드

Characterization of radioactive waste Radiochemistry Decommissioning Silver iodide Ettringite